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Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Investigation of Nuclide Importance to Functional Requirements Related to Transport and Long-Term Storage of LWR Spent Fuel

Author(s)
Broadhead, B. L. ,
DeHart, M. D. ,
Ryman, J. C. ,
Tang, J. S. ,
Parks, C. V.
Publication Date
The radionuclide characteristics of light-water-reactor (LWR) spent fuel play key roles in the design and licensing activities for radioactive waste transportation systems, interim storage facilities, and the final repository site.
burnup credit spent fuel transport lwr ornl/tm-12742 nuclide used fuel

Overview of the Nuclear Regulatory Commission and Its Regulatory Process for the Nuclear Fuel Cycle for Light Water Reactors

Overview of the Nuclear Regulatory Commission and Its Regulatory Process for the Nuclear Fuel Cycle for Light Water Reactors

Author(s)
Talisman International, LLC
Publication Date

This paper provides a brief description of the United States Nuclear Regulatory Commission (NRC) and its regulatory process for the current nuclear fuel cycle for light water power reactors (LWRs). It focuses on the regulatory framework for the licensing of facilities in the fuel cycle. The first part of the paper provides an overview of the NRC and its regulatory program including a description of its organization, function, authority, and responsibilities.

lwr nuclear fuel cycle light water reactor nrc licensing regulations blue ribbon commission

Evaluation of Measured LWR Spent Fuel Composition Data for Use in Code Validation End-User Manual

Evaluation of Measured LWR Spent Fuel Composition Data for Use in Code Validation End-User Manual

Author(s)
Murphy, B. C. ,
DeHart, M. D. ,
Hermann, O. W.
Publication Date

Burnup credit (BUC) is a concept applied in the criticality safety analysis of spent nuclear fuel
in which credit or partial credit is taken for the reduced reactivity worth of the fuel due to both fissile
depletion and the buildup of actinides and fission products that act as net neutron absorbers.
Typically, a two-step process is applied in BUC analysis: first, depletion calculations are performed
to estimate the isotopic content of spent fuel based on its burnup history; second, three-dimensional

burnup credit spent fuel ornl/m-6121 lwr code verification used fuel
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